Analysis of Neutron Fission Reaction Rate in the Nuclear Fuel Cell Using Collision Probability Method with Non Flat Flux Approach
Author:
Publisher
IOP Publishing
Subject
General Physics and Astronomy
Link
http://stacks.iop.org/1742-6596/877/i=1/a=012013/pdf
Reference8 articles.
1. Neutron Flux Interpolation with Finite Element Method in the Nuclear Fuel Cell Calculation using Collision Probability Method
2. Nuclear Fuel Cell Calculation Using Collision Probability Method with Linear Non Flat Flux Approach
3. Theoretical analysis of integral neutron transport equation using collision probability method with quadratic flux approach
Cited by 4 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Calculation of Collision Probability Matrix of Nuclear Fuel Cell as a Function of Neutron Energy Group Using Flat Flux Model;International Journal of Mechanics;2021-08-25
2. Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction;International Journal of Energy Research;2021-01-25
3. Neutron flux distribution calculation for various spatial mesh of finite slab geometry using one-dimensional diffusion equation;AIP Conference Proceedings;2019
4. The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method;MATEC Web of Conferences;2018
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